Zobrazeno 1 - 10
of 26
pro vyhledávání: '"Dong-Hak Kook"'
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 3, Pp 614-620 (2020)
In a previous study, delayed hydride cracking (DHC) assessment of pressurized water reactor (PWR) spent fuel during dry storage using the threshold stress intensity factor (KIH) was performed. However, there were a few limitations in the analysis of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::677073bac0ab2f0e9293caf0cd5f5c37
http://www.sciencedirect.com/science/article/pii/S1738573319303705
http://www.sciencedirect.com/science/article/pii/S1738573319303705
Publikováno v:
Journal of Nuclear Materials. 509:285-294
Hydride reorientation is one of the crucial degradation mechanisms of cladding integrity under dry storage conditions. Recently, it has been experimentally reported that the threshold stress triggering the reorientation depends on various factors syn
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5723c75a60200c4e323fb0736668f841
https://doi.org/10.1016/j.jnucmat.2018.07.005
https://doi.org/10.1016/j.jnucmat.2018.07.005
Publikováno v:
Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT). 16:243-260
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cf704a6cf08dd389bad4566523091252
https://doi.org/10.7733/jnfcwt.2018.16.2.243
https://doi.org/10.7733/jnfcwt.2018.16.2.243
Publikováno v:
Nuclear Technology. 203:282-292
One of the limiting mechanisms of pressurized water reactor spent fuel cladding is creep owing to high temperature and rod internal pressure. Based on extensive studies, many countries have tentatively concluded that creep rupture is hard to occur un
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2053734555ce814a8475bc3b150e23e5
https://doi.org/10.1080/00295450.2018.1448203
https://doi.org/10.1080/00295450.2018.1448203
Publikováno v:
Nuclear Engineering and Design. 322:324-330
One of the possible degradation mechanisms of PWR spent fuel cladding is delayed hydride cracking (DHC), which can activate within a relatively low temperature range. Due to the high crack growth rate, it is essential to prevent DHC crack growth, but
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eeacb0e25cd2560ec6f0ddad626b52d5
https://doi.org/10.1016/j.nucengdes.2017.07.015
https://doi.org/10.1016/j.nucengdes.2017.07.015
Publikováno v:
Journal of Nuclear Materials. 491:105-114
In order to fundamentally understand the secondary hydriding mechanism of zirconium alloy cladding, the reaction of commercial Zircaloy-4 tubes with hydrogen and steam mixture was studied using a thermo-gravimetric analyser with two variables, H2/H2O
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1ea7849b439410a6d228c74c2e6ae7ec
https://doi.org/10.1016/j.jnucmat.2017.05.004
https://doi.org/10.1016/j.jnucmat.2017.05.004
Publikováno v:
Journal of Nuclear Materials. 492:253-259
Temperature and hoop stress limits have been used to prevent the gross rupture of spent nuclear fuel during dry storage. The stress due to rod internal pressure can induce cladding degradation such as creep, hydride reorientation, and delayed hydride
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fd8ef7c7e915a8579b61831fb53a0402
https://doi.org/10.1016/j.jnucmat.2017.05.047
https://doi.org/10.1016/j.jnucmat.2017.05.047
Publikováno v:
Journal of Nuclear Materials. 543:152596
The delayed hydride cracking (DHC) is becoming important because of its extended long-term dry storage and lower dry storage temperature than expected. However, it remains difficult to predict the DHC behavior of PWR spent fuel cladding due to the li
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ceaf56f698b610ea6e3acad220e9bd32
https://doi.org/10.1016/j.jnucmat.2020.152596
https://doi.org/10.1016/j.jnucmat.2020.152596
Autor:
Yang-Il Jung, Hyun-Gil Kim, Sang-Chae Jeon, Jae Ho Yang, Dong-Joo Kim, Dong-Hak Kook, Dong Seok Kim, Kun-Woo Song, Changhwan Shin, Keon-Sik Kim, Yang-Hyun Koo
Publikováno v:
Journal of Nuclear Materials. 527:151801
Following the Fukushima accident in March 2011, Korea Atomic Energy Research Institute (KAERI) has developed micro-cell fuel pellets for the purpose of reducing gas release, both stable and radioactive, not only under accident conditions, but during
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9cbfa37d0db49a47c4a8d33cbed63963
https://doi.org/10.1016/j.jnucmat.2019.151801
https://doi.org/10.1016/j.jnucmat.2019.151801
Publikováno v:
Korean Journal of Metals and Materials. 56
Zirconium-based alloys, widely used for nuclear fuel cladding, are highly susceptible to hydrideinduced embrittlement. The degree of the hydride embrittlement is strongly affected by not only its concentration but also its morphology. The hydride can
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::88327636bc8465a6f34c93898c71e9fc
https://doi.org/10.3365/kjmm.2018.56.2.79
https://doi.org/10.3365/kjmm.2018.56.2.79